ML20211P429
| ML20211P429 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/09/1997 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211P435 | List: |
| References | |
| NUDOCS 9710200191 | |
| Download: ML20211P429 (4) | |
Text
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p nnaru p
t UNITED STATES j
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 6 j
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DUKE ENERGY CORPORATION NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-413 CATAWBA _ NUCLEAR STATION. UNVT 1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.162 License No. NPF-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Energy Comoration, acting for hself, North Carolina Electric Memberchip Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated May 8,1997, and supplemented by letter dated September 10,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and scfety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
m 9710200191 971009 ADOCK0500g13 PDR P
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. 2.
Accordingly, the license is hereby amended by page changes to the Techni$al Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby amended to read as follows:
(2)
Technical Scecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.162. which are attached hereto, are hereby incorporated into this license. Duke Energy Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
4 l
H bert N. Berkow, Director Project Directorate ll-2 Divisie.1 of Reactor Projects - 1/11 Office of Nuclear Reactor Reguistion
Attachment:
Technical Specification Changes Date of issuance:
October 9, 1997
(
6HACHMENT TO LICENSE AMENDMENT NO.162 FACILITY OPERATING LICENSE NO. NPF-35 r
DOCKET NO. 50-413 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the areas of change, Remove Insert 3/4 4 2 3/4 4-2 h
i l
t i.
HOT STANDBY M G CONDITION FOR C+ ERAT 10N 3.4.1.2 At least three of the reactor coolant loops listed below shall be OPERABLE and in operation:*
Reactor Coolant Loop A and its associated steam generator and reactor a.
coolant pump, b.
Reactor Coolant loop B and its associated steam generator and reactor coolant pump, Reactor Coolant Loop C and its associated stea:a generator and reactor c.
coolant pump, and d.
Reactor Coolant loop D and its associated steam generator and reactor coolant pump.
8E.PLICABILITY: MODE 3.
ACTION:
With less than the above required reactor coolant loops OPERABLE, a.
restore the required loo)s to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within tie next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With less than the above required coolant loop in operation, restore the required loops to operation within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or open the Reactor Trip System breakers.
With no reactor coolant loops in operation, suspend all operations c.
involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required reactor coolant lo' ops to operation.
SURVEILLANCE REQUIREMENTS 4.4.1.2.1 The required steam generators shall be determined OPERABLE by
-verifying secondary side water level to be greater than or equal to 12% at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.4.1~.2.2 At least 3 reactor coolant loops shall be verified in operation and-circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- All reactor coolant pumps may be deenergized for up to I hour (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> on a one time basis for natural circulation testing following steam generator replacement) provided:
(1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is r.aintained at least 10*F below saturation temperature.
CATAWBA - UNIT 1 3/4 4-2 Amendment No. 162
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